http://wiki.fusenet.eu/fusionwiki/api.php?action=feedcontributions&feedformat=atom&user=DaniellopezbrunaFusionWiki - User contributions [en]2026-05-19T04:49:35ZUser contributionsMediaWiki 1.43.3http://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8198ASTRA2025-03-05T12:17:26Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with [[Magnetic island|magnetic islands]],” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by [[Magnetic island|magnetic islands]] or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and [[FAFNER|FAFNER]] to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8197ASTRA2025-03-05T12:12:55Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with [[Magnetic island|magnetic islands]],” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by [[Magnetic island|magnetic islands]] or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8196ASTRA2025-03-05T12:11:25Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with [[Magnetic island|magnetic islands]],” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8195ASTRA2025-03-05T12:06:03Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8194ASTRA2025-03-05T11:52:35Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. López-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Informe Técnico Ciemat 1402, CIEMAT, Madrid, May 2017</ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8193ASTRA2025-03-05T11:51:22Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. L ́opez-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Tech. Rep. 1402, CIEMAT, Madrid, May 2017</ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8192ASTRA2025-03-05T11:51:02Z<p>Daniellopezbruna: /* Extensions of ASTRA for the TJ-II stellarator */</p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
<br />
As an extension of the geometrical possibilities in ASTRA, plasma regions occupied by magnetic islands or ergodic regions (limited by flux surfaces) can be treated as well in the transport models<ref>D. L ́opez-Bruna, B. Momo, and Y. Zhang, “One-dimensional treatment of the effect of small magnetic islands on transport in the TJ-II stellarator,” Tech. Rep. 1402, CIEMAT, Madrid, May 2017<\ref>.<br />
<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8191ASTRA2025-03-05T11:43:26Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 dedicated subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8190ASTRA2025-03-05T11:42:22Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions<ref>D. López-Bruna, B. Momo, I. Predebon, A. López-Fraguas, F. Auriemma, Y. Suzuki, and R. Lorenzini, “Flux-surface averaged radial transport in toroidal plasmas with magnetic islands,” Nuclear Fusion, vol. 58, no. 10, p. 106031, 2018. [http://stacks.iop.org/0029-5515/58/i=10/a=106031]</ref>.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8189ASTRA2025-03-05T11:39:46Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined. In this case, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220 subroutines] can be added to update at will the metric coefficients depending on the plasma currents. Moreover, despite the one-dimensional nature of the transport equations, appropriate handling of the integration space permits also making calculations that include magnetic islands or ergodic plasma regions.<br />
<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [https://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8188ASTRA2025-03-03T14:39:25Z<p>Daniellopezbruna: Update of references with documentation purposes</p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [http://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref>.<br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8187ASTRA2025-03-03T14:36:45Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]]. It considers diagonal metric coefficients as it corresponds to axi-symmetric, tokamak-like geometries.<br />
<br />
<br />
Presently, the code is used for transport simulations of both [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be solved to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [http://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, ''Transporte con Astra en TJ-II,'' Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including possible changes of the main metric coefficients depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref><br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [https://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8186ASTRA2025-03-03T14:22:08Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref> <br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]].<br />
<br />
<br />
Presently, the code is used for transport simulations of [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be used to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [http://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, “Transporte con Astra en TJ-II,” Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including the possible variations of the main metric profiles of the magnetic configuration depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources for the [http://fusionwiki.ciemat.es/wiki/TJ-II TJ-II] device; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref><br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [http://www.ipp.mpg.de/~git/astra/section.php?sec=0 ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8185ASTRA2025-03-03T14:20:50Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]].<br />
<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref><br />
<br />
Presently, the code is used for transport simulations of [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be used to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. Examples of how the ASTRA suit can be extended for particular needs can be found below for the case of the TJ-II Heliac at [http://www.ciemat.es CIEMAT].<br />
<br />
== Extensions of ASTRA for the TJ-II stellarator ==<br />
<br />
ASTRA has been used in many transport analysis works related with the TJ-II device. The citations that follow contain the coding of ASTRA models, so they can serve as a reference for the extension of ASTRA to particular needs, as well as a source of examples of ASTRA programming.<br />
<br />
The ASTRA suite was adopted to perform interpretative and predictive transport for TJ-II plasmas considering an approximate geometry<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, “Transporte con Astra en TJ-II,” Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref>. The geometry was improved in collaboration with G. Pereverzev, one of the authors of the ASTRA suite, in order to adapt the non axi-symmetric stellarator geometry<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref>, which allowed for first estimates of the evolution of the rotational transform according to the net plasma current in the device. A more detailed evolution of the rotational transform, including the possible variations of the main metric profiles of the magnetic configuration depending on the evolution of the plasma pressure has been also programmed in ASTRA<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref>. In this case, internal and driven currents (e. g. bootstrap currents or heating-driven currents) can be included in the calculations.<br />
<br />
Demanding calculations are conveniently done through system calls from the ASTRA subroutines. One such possible extensions of the ASTRA is the coupling of the calculations to the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources for the [http://fusionwiki.ciemat.es/wiki/TJ-II TJ-II] device; or the coupling to ray-tracing calculations, including the access to distributed resources<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref><br />
<br />
<br />
<br />
<br />
== See also ==<br />
<br />
* [http://www.ipp.mpg.de/~git/astra/section.php?sec=0 ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
<br />
<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=8184ASTRA2025-03-03T13:12:58Z<p>Daniellopezbruna: /* References */</p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]].<br />
<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref><br />
<br />
Presently, the code is used for transport simulations of [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be used to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. An example of how the ASTRA suit can be extended for particular needs can be found [http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/41/046/41046471.pdf here] (In Spanish), where subroutines have been developed to couple the set of transport equations with the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources for the [http://fusionwiki.ciemat.es/wiki/TJ-II TJ-II] device.<br />
<br />
== See also ==<br />
<br />
* [http://www.ipp.mpg.de/~git/astra/section.php?sec=0 ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<ref>D. López-Bruna, F. Castejón, and J. M. Fontdecaba, “Transporte con Astra en TJ-II,” Informe Técnico Ciemat 1035, Ciemat, Madrid, Spain, Enero 2004, [https://inis.iaea.org/records/rcnnh-d2398]</ref><br />
<ref>D. López-Bruna, J. A. Romero, and F. Castejón, “Geometría del TJ-II en astra 6.0,” Informe Técnico Ciemat 1086, CIEMAT, Madrid, August 2006., [https://inis.iaea.org/records/xxs57-qjb22]</ref><br />
<ref>D. López-Bruna, J. M. Reynolds, A. Cappa, J. Martinell, J. García, and C. Gutiérrez-Tapia, “Programas periféricos de ASTRA para el TJ-II,” Informe Técnico Ciemat 1201, CIEMAT, March 2010, [https://documenta.ciemat.es/bitstream/123456789/114/1/40921_IC1201.pdf]</ref><br />
<ref>D. López-Bruna, J. M. Reynolds-Barredo, and B. Momo, “Evolution of the rotational transform in TJ-II discharges using the ASTRA code,” Informe Técnico Ciemat 1470, Ciemat, July 2020, [https://servicios.mpr.es/VisorPublicaciones/visordocumentosicopo.aspx?NIPO=83220004X&SUBNIPO=0001&IDPUBLICACION=000183220]</ref><br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=Coordinated_Working_Group_Meeting&diff=5319Coordinated Working Group Meeting2017-01-12T10:06:42Z<p>Daniellopezbruna: </p>
<hr />
<div>The [[Coordinated Working Group]] Meeting (CWGM) implements and coordinates international collaborations in [[Stellarator|stellarator-heliotron]] research.<br />
The work is intended to contribute to the [[Fusion_databases|International Stellarator-Heliotron Confinement (Profile) Database, ISH-C(P)DB]].<br />
The Coordinated Working Group Meeting and related database activities ISHPDB are being conducted under the auspices of the IEA Implementing Agreement of Development of Stellarator/Heliotron Concepts (2.10.1992).<br />
<br />
== List of meetings ==<br />
<br />
* [http://p-grp.nucleng.kyoto-u.ac.jp/ktscwgm2006/ 1<sup>st</sup> CWGM, Kyoto 2006]<br />
* [http://www.ipp.mpg.de/~dinklage/CWGM2007/cwgm.html 2<sup>nd</sup> CWGM, Greifswald 2007]<br />
* [http://ishcdb.nifs.ac.jp/program.html 3<sup>rd</sup> CWGM, Toki, 2007]<br />
* [http://www-fusion.ciemat.es/cwgm4/index.htm 4<sup>th</sup> CWGM, Madrid, 2008]<br />
* [http://www.ipf.uni-stuttgart.de/cwgm/index.html 5<sup>th</sup> CWGM, Stuttgart, 2009]<br />
* [http://www.pppl.gov/conferences/2009/ISHW09/CWGM.html 6<sup>th</sup> CWGM, 2009]<br />
* [http://www.ipp.mpg.de/~dinklage/CWGM7/ 7<sup>th</sup> CWGM, Greifswald, 2010]<br />
* [http://ishcdb.nifs.ac.jp/cwgm8.html 8<sup>th</sup> CWGM, Toki, 2011]<br />
* [http://iscdb.nifs.ac.jp/cwgm9.html 9<sup>th</sup> CWGM, Canberra, Australia, January 28, 2012]<br />
* [http://ishcdb.nifs.ac.jp/cwgm10.html 10<sup>th</sup> CWGM, Greifswald, Germany, 6-8 June, 2012]<br />
* [http://fusionsites.ciemat.es/cwgm11 11<sup>th</sup> CWGM, Madrid, Spain, 11-13 March 2013]<br />
* [http://ishcdb.nifs.ac.jp/CWGM12/index.html 12<sup>th</sup> CWGM, Padova, Italy, 20 September 2013] (at the 19<sup>th</sup> [[International Stellarator and Heliotron Workshop]])<br />
* [http://ishcdb.nifs.ac.jp/CWGM13/index.html 13<sup>th</sup> CWGM, Kyoto, Japan, 26-28 February 2014]<br />
* [http://ishcdb.nifs.ac.jp/CWGM14/index.html 14<sup>th</sup> CWGM, Warsaw, Poland, 17-19 June, 2015]<br />
* [http://www.ipp.mpg.de/cwgm 15<sup>th</sup> CWGM, Greifswald, Germany, 21-23 March, 2016]<br />
* [http://fusionsites.ciemat.es/cwgm16 16<sup>th</sup> CWGM, Madrid, Spain, 18-20 January, 2017]<br />
<br />
[[Category:Conferences]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=TJ-II:Langmuir_Probes&diff=4751TJ-II:Langmuir Probes2014-10-22T09:43:39Z<p>Daniellopezbruna: </p>
<hr />
<div>[[File:TJ-II_Langmuir.png|400px|thumb|right|Location of the reciprocating Langmuir probes at TJ-II]]<br />
[[TJ-II]] has two fast reciprocating drives for [[:Wikipedia:Langmuir probe|Langmuir probes]] (with a displacement velocity of approximately 1 m/s).<br />
<ref>[http://link.aip.org/link/?RSINAK/70/415/1 M.A. Pedrosa et al, ''Fast movable remotely controlled Langmuir probe system'', Rev. Sci. Instrum. '''70''' (1999) 415]</ref><br />
<ref>[http://dx.doi.org/10.1002/ctpp.200410104 E. Calderón et al, ''On the Influence of Probe Presheath on the Measurement of Fluctuation and E × B Turbulent Transport by Langmuir Probes'', Contributions to Plasma Physics '''44''', Issue 7-8 (2004) 700 - 704]</ref><br />
<ref>[http://link.aps.org/doi/10.1103/PhysRevLett.100.215003 M.A. Pedrosa et al, ''Evidence of Long-Distance Correlation of Fluctuations during Edge Transitions to Improved-Confinement Regimes in the TJ-II Stellarator'', Phys. Rev. Lett. '''100''' (2008) 215003]</ref><br />
Probe drive 1 is located at &phi; = 38.2&deg;, R=134 cm ([[TJ-II:Sectors|sector]] D4) and probe drive 2 at &phi; = 195&deg; ([[TJ-II:Sectors|sector]] B2).<br />
<br />
== Probe heads ==<br />
<br />
Several different heads can be mounted on the reciprocating drives: e.g., staircase Langmuir probes, a rake probe (as of 2009), or a multi-pin Langmuir probe (2010). A [[TJ-II:Biasing probe|biasing probe]] has also been used.<br />
<br />
{| border="0" style="width:450px;"<br />
|- valign="top"<br />
| [[File:Langmuir_probe_head.gif|200px|thumb|left|Photo of a staircase Langmuir probe head with three sets of measurement pins]]<br />
| [[File:Multipin.jpg|200px|thumb|left|Photo of a multipin Langmuir probe head]]<br />
|- <br />
| colspan="2" | [[File:TJ-II_Rake.png|450px|thumb|left|Photo of a Langmuir rake probe head]]<br />
|-<br />
|}<br />
<br />
== See also ==<br />
<br />
* [[TJ-II:Limiter|Limiter probes]]<br />
<br />
== References ==<br />
<references /></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=EIRENE&diff=4694EIRENE2014-07-18T14:58:56Z<p>Daniellopezbruna: </p>
<hr />
<div><br />
<br />
The EIRENE neutral gas transport code (...) resorts to a combinatorial discretisation of general 3 dimensional computational domains. It is a multi-species code solving simultaneously a system of time dependent (optional) or stationary (default) linear kinetic transport equations of almost arbitrary complexity. A crude model for transport of ionized particles along magnetic field lines is also included. EIRENE is coupled to external databases for atomic and molecular data and for surface reflection data, and it calls various user supplied routines, e.g. for exchange of data with other (fluid-) transport codes. The main goal of code development was to provide a tool to investigate neutral gas transport in magnetically confined plasmas. But, due to its flexibility, it also can be used to solve more general linear kinetic transport equations, by applying a stochastic rather than a numerical or analytical method of solution. In particular, options are retained to reduce the model equations to the theoretically important case of the one speed transport problem. Major applications of EIRENE are in connection with plasma fluid codes, in particular with the various versions of the B2 code. The semi-implicit iterative coupling method of B2- EIRENE and it’s implementation (code segment: EIRCOP) are also described. (Extracted from [http://www.eirene.de The Eirene Code User Manual]).<br />
<br />
Extensive documentation about the code can be found in the EIRENE Code [http://www.eirene.de EIRENE home] page, including the manual and [http://www.eirene.de/html/relevant_reports.html reports] on its coupling to transport codes.<br />
<br />
== References ==<br />
<references/><br />
<br />
* [http://www.eirene.de D. Reiter, The Eirene Code User Manual, Version: 11/2005]<br />
* B. Braams. Computational Studies in Tokamak Equilibrium and Transport. PhD thesis, Rijksuniversiteit Utrecht, June 1986<br />
* [http://iopscience.iop.org/0741-3335/33/13/008 D. Reiter, H. Kever, G.H. Wolf, et al. Helium removal from tokamaks. Plasma Phys. and Contr. Fus., 33:1579, 1991]<br />
* [http://www.sciencedirect.com/science/article/pii/S0022311506800140 D. Reiter. Progress in 2-dimensional plasma edge modelling. J. Nucl. Mat., 196– 198:241, 1992]<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=EIRENE&diff=4693EIRENE2014-07-18T14:45:23Z<p>Daniellopezbruna: /* References */</p>
<hr />
<div>[http://www.eirene.de EIRENE home]<br />
<br />
The EIRENE neutral gas transport code (...) resorts to a combinatorial discretisation of general 3 dimensional computational domains. It is a multi-species code solving simultaneously a system of time dependent (optional) or stationary (default) linear kinetic transport equations of almost arbitrary complexity. A crude model for transport of ionized particles along magnetic field lines is also included. EIRENE is coupled to external databases for atomic and molecular data and for surface reflection data, and it calls various user supplied routines, e.g. for exchange of data with other (fluid-) transport codes. The main goal of code development was to provide a tool to investigate neutral gas transport in magnetically confined plasmas. But, due to its flexibility, it also can be used to solve more general linear kinetic transport equations, by applying a stochastic rather than a numerical or analytical method of solution. In particular, options are retained to reduce the model equations to the theoretically important case of the one speed transport problem. Major applications of EIRENE are in connection with plasma fluid codes, in particular with the various versions of the B2 code. The semi-implicit iterative coupling method of B2- EIRENE and it’s implementation (code segment: EIRCOP) are also described. (Extracted from [http://www.eirene.de The Eirene Code User Manual]).<br />
<br />
<br />
== References ==<br />
<references/><br />
<br />
* [http://www.eirene.de D. Reiter, The Eirene Code User Manual, Version: 11/2005]<br />
* B. Braams. Computational Studies in Tokamak Equilibrium and Transport. PhD thesis, Rijksuniversiteit Utrecht, June 1986<br />
* [http://iopscience.iop.org/0741-3335/33/13/008 D. Reiter, H. Kever, G.H. Wolf, et al. Helium removal from tokamaks. Plasma Phys. and Contr. Fus., 33:1579, 1991]<br />
* [http://www.sciencedirect.com/science/article/pii/S0022311506800140 D. Reiter. Progress in 2-dimensional plasma edge modelling. J. Nucl. Mat., 196– 198:241, 1992]<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=EIRENE&diff=4692EIRENE2014-07-17T15:17:15Z<p>Daniellopezbruna: /* References */</p>
<hr />
<div>[http://www.eirene.de EIRENE home]<br />
<br />
== References ==<br />
<references/><br />
<br />
* [http://www.eirene.de D. Reiter, The Eirene Code User Manual, Version: 11/2005]<br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=4691ASTRA2014-07-17T15:12:32Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]].<br />
<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref><br />
<br />
Presently, the code is used for transport simulations of [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be used to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. An example of how the ASTRA suit can be extended for particular needs can be found [http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/41/046/41046471.pdf here] (In Spanish), where subroutines have been developed to couple the set of transport equations with the Montecarlo codes [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources for the [http://fusionwiki.ciemat.es/wiki/TJ-II TJ-II] device.<br />
<br />
== See also ==<br />
<br />
* [http://www.ipp.mpg.de/~git/astra/section.php?sec=0 ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=ASTRA&diff=4690ASTRA2014-07-17T15:10:09Z<p>Daniellopezbruna: </p>
<hr />
<div>The code ASTRA (Automated System for TRansport Analysis)<br />
solves a user-defined set of transport equations in <br />
[[Toroidal coordinates|toroidal geometry]].<br />
<ref>G.V. Pereverzev, P.N. Yushmanov, ''ASTRA - Automated System for TRansport Analysis'', Max-Planck-Institut Für Plasmaphysik, [http://w3.pppl.gov/~hammett/work/2009/Astra_ocr.pdf IPP-Report, IPP 5/98, February, 2002]</ref><br />
<br />
Presently, the code is used for transport simulations of [[Tokamak|tokamak]] and [[Stellarator|stellarator]] plasmas. If used for tokamak plasmas, the Grad-Shafranov equation can be used to update the geometry as the plasma current density and pressure evolve. In the case of stellarators, the geometry can be taken from experimental files where the most relevant metric coefficients and magnitudes are defined.<br />
<br />
ASTRA includes an extended library of physical modules, a graphic interface, plotting and post-run viewing facilities, etc. Along with the common libraries, every user can have his local libraries of different formulae and functions, experimental data and simulation results. The physics models are defined by the user through a high level programming language –ASTRA specific, but easy to learn– where the different formulae and functions can be directly included from the libraries. In addition, there is a set of subroutines that can be plugged into the models, thus allowing for complex evaluations of e.g. source terms. Subroutines can also be created by the user: every time ASTRA is run, it checks for modifications of the ASTRA environment (functions, formulae, subroutines... ) so the corresponding objects are compiled and included in the ASTRA framework for immediate use. An example of how the ASTRA suit can be extended for particular needs can be found [http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/41/046/41046471.pdf here] (In Spanish), where subroutines have been developed to couple the set of transport equations with [http://fusionwiki.ciemat.es/wiki/EIRENE Eirene] and Fafner to obtain respectively recycling and [http://fusionwiki.ciemat.es/wiki/TJ-II:Neutral_Beam_Injection neutral beam injection] sources for the [http://fusionwiki.ciemat.es/wiki/TJ-II TJ-II] device.<br />
<br />
== See also ==<br />
<br />
* [http://www.ipp.mpg.de/~git/astra/section.php?sec=0 ASTRA online manual]<br />
<br />
== References ==<br />
<references /><br />
<br />
[[Category:Software]]</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=Coordinated_Working_Group:_Neoclassical_Transport&diff=4566Coordinated Working Group: Neoclassical Transport2014-02-17T10:34:15Z<p>Daniellopezbruna: /* Central Electron Root Confinement */</p>
<hr />
<div>== Core Electron Root Confinement ==<br />
[https://ishpdb.ipp-hgw.mpg.de/ISS/public/ISHPDB_public/physicsTopics/CERC/index.html ISHPDB CERC]<br />
=== References ===<br />
M. Yokoyama et al., [[doi:10.1088/0029-5515/47/9/018|Nucl. Fusion., 47, 1213 (2007)]].<br><br />
M. Yokoyama et al., [http://www.new.ans.org/pubs/journals/fst/a_1254 Fusion Sci. Tech., 50, 327 (2006)].<br><br />
J. Lore et al., [[doi:10.1063/1.3300465|Physics of Plasmas 17, 056101 (2010)]]. <br><br />
<br />
== Ion Root Conditions ==<br />
[https://ishpdb.ipp-hgw.mpg.de/ISS/public/ISHPDB_public/physicsTopics/neocl_transp/index.html ISHPDB NC Ion Root Transport]<br />
<br />
=== References ===<br />
A. Dinklage et al., [http://dx.doi.org/10.1088/0029-5515/53/6/063022| Nucl. Fusion. 53, 063022 (2013)].<br></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=TJ-II:Electron_Cyclotron_Resonant_Heating&diff=4557TJ-II:Electron Cyclotron Resonant Heating2014-02-06T12:01:47Z<p>Daniellopezbruna: </p>
<hr />
<div>In the [[TJ-II]] stellarator, the plasmas are created and heated by two 53.2 GHz gyrotrons, each of them delivering up to 300 kW in the 2<sup>nd</sup> harmonic, with X-mode polarisation.<br />
<ref>[http://dx.doi.org/10.1088/0741-3335/30/7/008 F. Castejón and J. Guasp, ''Microwave injection in heliac device TJ-II'', Plasma Phys. Control. Fusion '''30''' (1988) 907-911]</ref><br />
The power is transmitted to the plasma by two quasi-optical transmission lines (QTL1 and QTL2).<br />
<ref>[http://dx.doi.org/10.1023/A:1006720117520 A. Fernández et al, ''Quasioptical Transmission Lines for ECRH at TJ-II Stellarator'', International Journal of Infrared and Millimeter Waves '''21''', 12 (2000) 1945-1957]</ref> <br />
The power is delivered to the [[TJ-II:Sectors|sector]] B3 (for QTL1) and A6 (for QTL2).<br />
The last mirror of each line is a steerable mirror located inside the [[TJ-II:Vacuum system|vacuum vessel]], which allows for perpendicular and oblique injection. <br />
<ref>[http://dx.doi.org/10.1109/ICIMW.2000.892950 A. Fernández et al, ''Design of the upgraded TJ-II quasi-optical transmission line'', Conference Digest, 25<sup>th</sup> International Conference on Infrared and Millimeter Waves (2000) 91 - 92]</ref><br />
<ref>[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?tp=&arnumber=4516800&isnumber=4516365 A. Fernandez et al, ''EC waves polarization control in the TJ-II stellarator'', Joint 32<sup>nd</sup> International Conference on Infrared and Millimeter Waves (2007)]</ref><br />
<ref>[http://dx.doi.org/10.1007/s10762-007-9256-2 A. Fernández et al, ''Gyrotron Radiation Affected by a Controlled Modulated Reflector: High Power Experiment'', International Journal of Infrared and Millimeter Waves '''28''', 9 (2007) 705-711]</ref><br />
<ref>[http://dx.doi.org/10.1016/j.fusengdes.2008.12.092 A. Fernández et al, ''Performance of the TJ-II ECRH system with the new −80 kV 50 A high voltage power supply'', Fusion Engineering and Design '''84''', Issues 2-6 (2009) 772-775]</ref><br />
The gyrotrons can be modulated for perturbative transport experiments <ref>[http://stacks.iop.org/PPCF/45/105 S. Eguilior et al, ''Heat wave experiments on TJ-II flexible heliac'', Plasma Phys. Control. Fusion '''45''' (2003) 105–120]</ref> and can be used to drive current.<br />
<ref>[http://dx.doi.org/10.1088/0741-3335/40/12/010 V. Tribaldos et al, ''Electron cyclotron heating and current drive in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''40''' (1998) 2113]</ref><br />
<br />
== References ==<br />
<references /></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=TJ-II:Electron_Cyclotron_Resonant_Heating&diff=4556TJ-II:Electron Cyclotron Resonant Heating2014-02-06T11:58:38Z<p>Daniellopezbruna: </p>
<hr />
<div>In the [[TJ-II]] stellarator, the plasmas are created and heated by two 53.2 GHz gyrotrons, each of them delivering up to 300 kW in the 2<sup>nd</sup> harmonic, with X-mode polarisation.<br />
<ref>[http://dx.doi.org/10.1088/0741-3335/30/7/008 F. Castejón and J. Guasp, ''Microwave injection in heliac device TJ-II'', Plasma Phys. Control. Fusion '''30''' (1988) 907-911]</ref><br />
The power is transmitted to the plasma by two quasi-optical transmission lines (QTL1 and QTL2).<br />
<ref>[http://dx.doi.org/10.1023/A:1006720117520 A. Fernández et al, ''Quasioptical Transmission Lines for ECRH at TJ-II Stellarator'', International Journal of Infrared and Millimeter Waves '''21''', 12 (2000) 1945-1957]</ref> <br />
The power is delivered to the [[TJ-II:Sectors|sector]] B3 (for QTL1) and A6 (for QTL2).<br />
The last mirror of each line is a steerable mirror located inside the [[TJ-II:Vacuum system|vacuum vessel]], which allows for perpendicular and oblique injection. <br />
<ref>[http://dx.doi.org/10.1109/ICIMW.2000.892950 A. Fernández et al, ''Design of the upgraded TJ-II quasi-optical transmission line'', Conference Digest, 25<sup>th</sup> International Conference on Infrared and Millimeter Waves (2000) 91 - 92]</ref><br />
<ref>[http://ieeexplore.ieee.org/xpl/freeabs_all.jsp?tp=&arnumber=4516800&isnumber=4516365 A. Fernandez et al, ''EC waves polarization control in the TJ-II stellarator'', Joint 32<sup>nd</sup> International Conference on Infrared and Millimeter Waves (2007)]</ref><br />
<ref>[http://dx.doi.org/10.1007/s10762-007-9256-2 A. Fernández et al, ''Gyrotron Radiation Affected by a Controlled Modulated Reflector: High Power Experiment'', International Journal of Infrared and Millimeter Waves '''28''', 9 (2007) 705-711]</ref><br />
<ref>[http://dx.doi.org/10.1016/j.fusengdes.2008.12.092 A. Fernández et al, ''Performance of the TJ-II ECRH system with the new −80 kV 50 A high voltage power supply'', Fusion Engineering and Design '''84''', Issues 2-6 (2009) 772-775]</ref><br />
The gyrotrons can be modulated for perturbative transport experiments<br />
<ref>[http://stacks.iop.org/PPCF/45/105 S. Eguilior et al, ''Heat wave experiments on TJ-II flexible heliac'', Plasma Phys. Control. Fusion 45 (2003) 105–120]</ref><br />
and can be used to drive current.<br />
<ref>[http://dx.doi.org/10.1088/0741-3335/40/12/010 V. Tribaldos et al, ''Electron cyclotron heating and current drive in the TJ-II stellarator'', Plasma Phys. Control. Fusion 40 (1998) 2113]</ref><br />
<br />
== References ==<br />
<references /></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=FusionWiki:Current_events&diff=4555FusionWiki:Current events2014-02-05T19:18:55Z<p>Daniellopezbruna: Corregida ciudad del evento (S. José en vez de S. Carlos)</p>
<hr />
<div>== Upcoming Fusion and Plasma events ==<br />
<br />
Please feel free to add events.<br />
<br />
=== 2014 ===<br />
<br />
{| class="wikitable" style="width: 100%" border="1"<br />
|-<br />
! scope="col" width="20%" | Date (2014)<br />
! scope="col" width="20%" | Location<br />
! scope="col" width="60%" | Conference/Meeting<br />
|-<br />
| January 27-31 || San José, Costa Rica || [http://lawpp2014.org/ 15<sup>th</sup> Latin American Workshop on Plasma Physics (LAWPP)]<br />
|-<br />
| April 22-25 || San Antonio, Texas, US || [http://ttf2014.ucsd.edu/TTF_2014/Home.html US Transport Task Force Workshop]<br />
|-<br />
| May 26-30 || Kanazawa, Japan || [http://psi2014.nifs.ac.jp/ 21<sup>th</sup> International Conference on Plasma Surface Interactions (PSI)]<br />
|-<br />
| June 1-5 || Atlanta, USA || [http://web.ornl.gov/sci/fed/HTPD2014/ 20<sup>th</sup> Topical Conference on High-Temperature Plasma Diagnostics (HTPD)]<br />
|-<br />
| June 16-19 || Prague, Czech Republic || [http://www.plasmaconference.cz/about.php 26<sup>th</sup> Symposium on Plasma Physics and Technology]<br />
|-<br />
| June 23-27 || Berlin, Germany || [http://eps2014-berlin.de 41<sup>st</sup> European Physical Society Conference on Plasma Physics (EPS)]<br />
|-<br />
| September 8 - 11 || Abingdon, UK || [http://www.ttf2014.org/ 19<sup>th</sup> Joint EU-US Transport Task Force Workshop (TTF)]<br />
|-<br />
| September 29 - October 3 || San Sebastián, Spain || [http://www.soft2014.eu/ 28<sup>th</sup> Symposium on Fusion Technology (SOFT)]<br />
|-<br />
| October 13-18|| St. Petersburg, Russia || [http://www-pub.iaea.org/iaeameetings/46091/25th-Fusion-Energy-Conference-FEC-2014 25<sup>th</sup> IAEA Fusion Energy Conference (FEC)]<br />
|}<br />
<br />
=== 2015 ===<br />
<br />
{| class="wikitable" style="width: 100%" border="1"<br />
|-<br />
! scope="col" width="20%" | Date (2015)<br />
! scope="col" width="20%" | Location<br />
! scope="col" width="60%" | Conference/Meeting<br />
|-<br />
| October 5 - 8 || Lisbon, Portugal || [http://www.ipfn.ist.utl.pt/eftc2015 16<sup>th</sup> European Fusion Theory Conference (EFTC)]<br />
<br />
|}<br />
<br />
== Periodic meetings ==<br />
<br />
The following FusionWiki entries attempt to both provide a record of historic meetings and direct links to proceedings:<br />
* The [[IAEA Fusion Energy Conference]] (FEC)<br />
* The [[European Physical Society Conference on Plasma Physics]] (EPS-CPP)<br />
* The [[International Congress on Plasma Physics]] (ICPP)<br />
* The [http://www.apsdpp.org/meetings/meeting_archives.php Annual Meeting of the Division of Plasma Physics of the American Physical Society] (APS-DPP)<br />
* The [[International Stellarator and Heliotron Workshop]] (ISHW)<br />
* The [[European Fusion Theory Conference]] (EFTC)<br />
* The [[Conference on Plasma Surface Interactions]] (PSI)<br />
* The [[Symposium on Fusion Technology]] (SOFT)<br />
* The [[EU-US Transport Task Force Meeting]] (TTF)<br />
* The [[International Toki Conference]] (ITC)<br />
* The [[Topical Conference on High Temperature Plasma Diagnostics]] (HTPD)<br />
* The [http://www.sherwoodtheory.org/ Sherwood Theory Conference]<br />
* The [[International Conference on Tritium Science and Technology]] (TRITIUM)<br />
* The [[International Symposium on Fusion Nuclear Technology]] (ISFNT)<br />
* The [[Coordinated Working Group Meeting]] (CWGM)<br />
<br />
See also [[:Category:Conferences]].<br />
<br />
== Meeting lists at other sites ==<br />
<br />
* [http://www.ieee.org/plasma_meetings IEEE.org] (comprehensive list)<br />
* [http://fusenet.eu/events FuseNet Events]<br />
* [http://crpp.epfl.ch/conferences_e Centre de Recherches en Physique des Plasmas]<br />
* [http://fire.pppl.gov/meetings_fusion.htm Fusion meeting list at Fire]<br />
* [http://www.conference-service.com/conferences/plasma-and-gas-discharge-physics.html Conference-service] (commercial)</div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=Coordinated_Working_Group:_Neoclassical_Transport&diff=4515Coordinated Working Group: Neoclassical Transport2013-12-17T11:43:35Z<p>Daniellopezbruna: /* Ion Root Conditions */</p>
<hr />
<div>== Central Electron Root Confinement ==<br />
[https://ishpdb.ipp-hgw.mpg.de/ISS/public/ISHPDB_public/physicsTopics/CERC/index.html ISHPDB CERC]<br />
=== References ===<br />
M. Yokoyama et al., [[doi:10.1088/0029-5515/47/9/018|Nucl. Fusion., 47, 1213 (2007)]].<br><br />
M. Yokoyama et al., [http://www.new.ans.org/pubs/journals/fst/a_1254 Fusion Sci. Tech., 50, 327 (2006)].<br><br />
J. Lore et al., [[doi:10.1063/1.3300465|Physics of Plasmas 17, 056101 (2010)]]. <br><br />
<br />
== Ion Root Conditions ==<br />
[https://ishpdb.ipp-hgw.mpg.de/ISS/public/ISHPDB_public/physicsTopics/neocl_transp/index.html ISHPDB NC Ion Root Transport]<br />
<br />
=== References ===<br />
A. Dinklage et al., [http://dx.doi.org/10.1088/0029-5515/53/6/063022| Nucl. Fusion. 53, 063022 (2013)].<br></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=TJ-II:Electron_Cyclotron_Emission&diff=4000TJ-II:Electron Cyclotron Emission2012-07-02T15:27:40Z<p>Daniellopezbruna: Specifies that the ECE system is tuned to receive radiation mainly from the HFS of the plasma</p>
<hr />
<div>[[File:TJ-II_ECE_Antenna.png|315px|thumb|right|Diagram showing the position of the ECE antenna-mirror system at TJ-II.]]<br />
Electron temperature profiles are measured at [[TJ-II]]<br />
by means of a 16 channel heterodyne radiometer,<br />
covering the frequency range 50–60 GHz, corresponding to the second harmonic of electron cyclotron emission (ECE) in X-mode polarization at a magnetic field of 0.95 T on the plasma axis. <br />
The measurements are performed from the low field side (LFS) in the horizontal midplane (between [[TJ-II:Sectors|sectors]] C4 and C5, &phi; = 315&deg;), but most of the channels receive radiation from the high field side (HFS). In normal operation conditions, the frequency depends on a known way on the magnitude of the magnetic field B. Tuning properly the receiver system, each frequency corresponds to a different value of the major radius ''R'' (according to ''B(R)''). <br />
The system is operated close to the strong [[TJ-II:Electron Cyclotron Resonant Heating|ECR heating source]] (f<sub>ECRH</sub> = 53.2 GHz). <br />
To protect the radiometer against stray radiation from the gyrotron, the radiometer band is split into two parts. <br />
The second harmonic emission above and below 53.2 GHz are measured separately by means of microwave couplers in the signal path.<br />
<br />
== Calibration ==<br />
The system is calibrated absolutely by comparing room temperature with liquid nitrogen temperature. <br />
<ref name="Luna">[http://link.aip.org/link/?RSINAK/72/379/1 E. de la Luna, J. Sánchez, V. Tribaldos, and T. Estrada, ''Multichannel electron cyclotron emission radiometry in TJ-II stellarator'', Rev. Sci. Instrum. '''72''', 379 (2001)]</ref><br />
<ref>[http://dx.doi.org/10.1016/S0920-3796(00)00492-0 E. de la Luna et al, ''Electron cyclotron emission measurements on TJ-II stellarator plasmas'', Fusion Engineering and Design '''53''', Issues 1-4 (2001) 147-151]</ref><br />
The optical system and the transmission line of the ECE diagnostic were designed to allow the calibration to be performed outside the vacuum vessel keeping the arrangement of the diagnostic.<br />
To calibrate, the transmission line is opened close to the diagnostic port (C5-bottom). Then the port flange, which holds the optical system and the wave-guide up to that point, is extracted from the torus and assembled with the same alignment outside the vacuum vessel.<br />
A check for the radiometer stability is performed periodically by using a stable noise source at the input of the radiometer. Such a noise source is also used to test the linearity of the system and to calibrate any possible change that may occur in the electronics of the diagnostic.<br />
<br />
== Data analysis ==<br />
<br />
The emission can be simulated by the [[TRECE]] ray tracing code.<br />
<ref name="Tribal">[http://dx.doi.org/10.1088/0029-5515/36/3/I02 V. Tribaldos and B. P. van Milligen, ''Electron cyclotron emission calculations for TJ-II stellarator'', Nucl. Fusion '''36''', 283 (1996)]</ref><br />
<br />
The local radiation temperature is assumed to be a function only of the local electron temperature at the resonant layer; however, if the plasma is not Maxwellian or if the plasma is optically thin, the measured radiation temperature is no longer equal to the electron temperature. <br />
The effect of polarization rotation can be neglected once the correct polarization for the pure X mode on-axis is chosen. Even at high density (worst condition) the radiation coming from the plasma bulk experiences a rotation below 5&deg;.<ref name="Tribal" /><br />
The spatial resolution is about 1 cm.<ref name="Luna" /><br />
<br />
The typical sampling rate is 100 kHz.<br />
The raw signals in the [[TJ-II:Shot_database|TJ-II database]] are called 'ECE1' ... 'ECE16', and the processed (calibrated) signals 'TECE1_' ... 'TECE16_' (units: keV).<br />
<br />
== References ==<br />
<references /></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=TJ-II:Transport_and_magnetic_configuration&diff=3556TJ-II:Transport and magnetic configuration2011-09-08T18:19:57Z<p>Daniellopezbruna: </p>
<hr />
<div>A significant part of the research effort at [[TJ-II]] is dedicated to the study of the interaction between transport and the (flexible) magnetic configuration.<br />
<ref>[http://dx.doi.org/10.1088/0741-3335/41/12B/307 C. Alejaldre et al, ''Confinement studies in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''41''' (1999) B109]</ref><br />
<ref>[http://dx.doi.org/10.1088/0741-3335/45/3/304 M.A. Ochando et al, ''Emissivity toroidal asymmetries induced by ECRH driven convective fluxes in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''45''' (2003) 221-231]</ref><br />
<ref>[http://dx.doi.org/10.1088/0029-5515/45/10/S22 C. Hidalgo et al, ''Overview of TJ-II experiments'', Nucl. Fusion '''45''' (2005) S266-S275]</ref><br />
The following issues contribute to the influence of the configuration on confinement:<br />
* The rotational transform <ref>[http://dx.doi.org/10.1088/0029-5515/45/4/009 E. Ascasíbar et al, ''Magnetic configuration and plasma parameter dependence of the energy confinement time in ECR heated plasmas from the TJ-II stellarator'', Nucl. Fusion '''45''' (2005) 276-284]</ref><br />
* Rational surfaces <ref>[http://dx.doi.org/10.1209/0295-5075/82/65002 D. López-Bruna et al, ''Tracking magnetic resonances in the effective electron heat diffusivity of ECH plasmas of the TJ-II Heliac'', EuroPhysics Letters '''82''' (2008) 65002]</ref><ref>[http://doi:10.1088/0029-5515/49/8/085016 D. López-Bruna et al, ''First dynamic magnetic configuration scans in ECRH plasmas of the TJ-II Heliac'', Nucl. Fusion '''49''' (2009) 085016]</ref><ref>[http://dx.doi.org/10.1002/ctpp.200900005 D. López-Bruna et al, ''Magnetic Resonances in ECR-Heated Plasmas of the TJ-II Heliac'', Contrib. Plasma Phys. '''50''' (2010) 600]</ref><br />
* [[Magnetic shear]] <ref>[http://dx.doi.org/10.1088/0029-5515/43/6/301 J.A. Romero et al, ''Controlling confinement with induced toroidal current in the flexible Heliac TJ-II'', Nucl. Fusion '''43''' (2003) 387-392]</ref> <ref>[http://dx.doi.org/10.1088/0029-5515/44/5/008 D. López-Bruna et al, ''Effects of ohmic current in the TJ-II stellarator'', Nucl. Fusion '''44''', 5 (2004) 645-654]</ref><br />
* [[Magnetic well]] <ref>[http://dx.doi.org/10.1088/0741-3335/43/12A/324 C. Hidalgo et al, ''On the radial scale of fluctuations in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''43''' (2001) A313-A321]</ref> <ref>[http://link.aip.org/link/?PHPAEN/9/713/1 J. Castellano et al, ''Magnetic well and instability thresholds in the TJ-II stellarator'', Phys. Plasmas '''9''' (2002) 713]</ref> <ref>[http://dx.doi.org/10.1088/0741-3335/44/12B/322 E. Ascasíbar et al, ''Confinement and stability on the TJ-II stellarator'', Plasma Phys. Control. Fusion '''44''' (2002) B307-B322]</ref><br />
<br />
The picture emerging from these studies is complex. In general, the presence of low-order rational surfaces in the plasma does not seem to be deleterious for transport; rather, local reductions of transport are observed (except at very low shear). Possibly, this is associated with the formation of [[TJ-II:Internal Transport Barriers|internal transport barriers]] at or near such rational surfaces, a consequence of the modification of the radial electric field by the rational surfaces themselves. It is being investigated whether the plasmas where this has been studied have the conditions for a self-healing state of the corresponding magnetic perturbations. On the other hand, the reduction of the magnetic well clearly enhances turbulence levels.<br />
<br />
== References ==<br />
<references /></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=TJ-II:Transport_and_magnetic_configuration&diff=3555TJ-II:Transport and magnetic configuration2011-09-08T18:14:47Z<p>Daniellopezbruna: </p>
<hr />
<div>A significant part of the research effort at [[TJ-II]] is dedicated to the study of the interaction between transport and the (flexible) magnetic configuration.<br />
<ref>[http://dx.doi.org/10.1088/0741-3335/41/12B/307 C. Alejaldre et al, ''Confinement studies in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''41''' (1999) B109]</ref><br />
<ref>[http://dx.doi.org/10.1088/0741-3335/45/3/304 M.A. Ochando et al, ''Emissivity toroidal asymmetries induced by ECRH driven convective fluxes in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''45''' (2003) 221-231]</ref><br />
<ref>[http://dx.doi.org/10.1088/0029-5515/45/10/S22 C. Hidalgo et al, ''Overview of TJ-II experiments'', Nucl. Fusion '''45''' (2005) S266-S275]</ref><br />
The following issues contribute to the influence of the configuration on confinement:<br />
* The rotational transform <ref>[http://dx.doi.org/10.1088/0029-5515/45/4/009 E. Ascasíbar et al, ''Magnetic configuration and plasma parameter dependence of the energy confinement time in ECR heated plasmas from the TJ-II stellarator'', Nucl. Fusion '''45''' (2005) 276-284]</ref><br />
* Rational surfaces <ref>[http://dx.doi.org/10.1209/0295-5075/82/65002 D. López-Bruna et al, ''Tracking magnetic resonances in the effective electron heat diffusivity of ECH plasmas of the TJ-II Heliac'', EuroPhysics Letters '''82''' (2008) 65002]</ref><br />
<ref>[http://doi:10.1088/0029-5515/49/8/085016 D. López-Bruna et al, ''First dynamic magnetic configuration scans in ECRH plasmas of the TJ-II Heliac'', Nucl. Fusion '''49''' (2009) 085016]</ref><br />
<ref>[http://dx.doi.org/10.1209/0295-5075/82/65002 D. López-Bruna et al, ''Tracking magnetic resonances in the effective electron heat diffusivity of ECH plasmas of the TJ-II Heliac'', EuroPhysics Letters '''82''' (2008) 65002]</ref><br />
* [[Magnetic shear]] <ref>[http://dx.doi.org/10.1088/0029-5515/43/6/301 J.A. Romero et al, ''Controlling confinement with induced toroidal current in the flexible Heliac TJ-II'', Nucl. Fusion '''43''' (2003) 387-392]</ref> <ref>[http://dx.doi.org/10.1088/0029-5515/44/5/008 D. López-Bruna et al, ''Effects of ohmic current in the TJ-II stellarator'', Nucl. Fusion '''44''', 5 (2004) 645-654]</ref><br />
* [[Magnetic well]] <ref>[http://dx.doi.org/10.1088/0741-3335/43/12A/324 C. Hidalgo et al, ''On the radial scale of fluctuations in the TJ-II stellarator'', Plasma Phys. Control. Fusion '''43''' (2001) A313-A321]</ref> <ref>[http://link.aip.org/link/?PHPAEN/9/713/1 J. Castellano et al, ''Magnetic well and instability thresholds in the TJ-II stellarator'', Phys. Plasmas '''9''' (2002) 713]</ref> <ref>[http://dx.doi.org/10.1088/0741-3335/44/12B/322 E. Ascasíbar et al, ''Confinement and stability on the TJ-II stellarator'', Plasma Phys. Control. Fusion '''44''' (2002) B307-B322]</ref><br />
<br />
The picture emerging from these studies is complex. In general, the presence of low-order rational surfaces in the plasma does not seem to be deleterious for transport; rather, local reductions of transport are observed (except at very low shear). Possibly, this is associated with the formation of [[TJ-II:Internal Transport Barriers|internal transport barriers]] at or near such rational surfaces, a consequence of the modification of the radial electric field by the rational surfaces themselves. It is being investigated whether the plasmas where this has been studied have the conditions for a self-healing state of the corresponding magnetic perturbations. On the other hand, the reduction of the magnetic well clearly enhances turbulence levels.<br />
<br />
== References ==<br />
<references /></div>Daniellopezbrunahttp://wiki.fusenet.eu/fusionwiki/index.php?title=LNF:Plasma_Physics&diff=3554LNF:Plasma Physics2011-09-07T14:23:41Z<p>Daniellopezbruna: /* Research summaries */</p>
<hr />
<div>Plasma Physics is the main research topic at the [[Laboratorio Nacional de Fusión]].<br />
<br />
<br />
== Research topics ==<br />
<br />
=== Experiment ===<br />
* [[TJ-II:Transport and magnetic configuration|Transport and magnetic configuration]], iota effects<br />
* [[TJ-II:Confinement transitions|Confinement transitions]], zonal flows<br />
* [[TJ-II:Internal Transport Barriers|Internal Transport Barriers]]<br />
* [[TJ-II:Plasma Wall Interaction|Plasma Wall Interaction]]<br />
* [[TJ-II:Impurity transport|Impurity transport]]<br />
* [[TJ-II:Instabilities|Instabilities]]<br />
* [[TJ-II:Turbulence|Turbulence]]<br />
<br />
=== Theory ===<br />
<br />
* [[Neoclassical transport]]<br />
* [[Self-Organised Criticality]]<br />
* [[Non-diffusive transport]]<br />
* [[Gyrokinetic simulations]]<br />
* [[TJ-II:Divertor|Divertor studies for TJ-II]]<br />
* [[Topology and transport|Topology and transport (research project funded by the Ministerio de Ciencia e Innovación)]]<br />
<br />
== Research summaries ==<br />
<br />
* [[doi:10.1088/0741-3335/41/3A/047|C. Alejaldre et al, ''First plasmas in the TJ-II flexible Heliac'', Plasma Phys. Control. Fusion '''41''' (1999) A539-A548]]<br />
* [[doi:10.1088/0029-5515/41/10/312|C. Alejaldre et al, ''Review of confinement and transport studies in the TJ-II flexible heliac'', Nucl. Fusion '''41''' (2001) 1449-1457]] <br />
* [[doi:10.1016/S0920-3796(01)00237-X|E. Ascasíbar et al, ''Overview of TJ-II flexible heliac results'', Fusion Engineering and Design '''56-57''' (2001) 145-154]]<br />
* [[doi:10.1088/0741-3335/44/12B/322|E. Ascasíbar et al, ''Confinement and stability on the TJ-II stellarator'', Plasma Phys. Control. Fusion '''44''' (2002) B307-B322]]<br />
* [http://link.aip.org/link/?APCPCS/669/162/1 F. Castejón et al, ''Transport Properties in the TJ-II Flexible Heliac'', AIP Conf. Proc. '''669''' (2003) 162-165]<br />
* [[doi:10.1088/0029-5515/45/10/S22|C. Hidalgo et al, ''Overview of TJ-II experiments'', Nucl. Fusion '''45''' (2005) S266-S275]]<br />
* [http://link.aip.org/link/?APCPCS/875/357/1 D. López-Bruna et al, ''Overview of TJ-II experiments'', AIP Conf. Proc. '''875''' (2006) 357-362]<br />
* [[doi:10.1088/0029-5515/47/10/S16|J. Sánchez et al, ''Overview of TJ-II experiments'', Nucl. Fusion '''47''' (2007) S677-S685]]<br />
* [http://www-pub.iaea.org/MTCD/Meetings/FEC2008/ov_4-5.pdf J. Sánchez et al, ''Overview of TJ-II experiments'', Proc. Fusion Energy Conf. (2008)]<br />
* [[doi:10.1088/0029-5515/49/10/104018|J. Sánchez et al, ''Confinement transitions in TJ-II under Li-coated wall conditions'', Nucl. Fusion '''49''' (2009) 104018]]<br />
* [[doi:10.1002/ctpp.200900032|E. Ascasíbar et al, ''Global energy confinement studies in TJ-II NBI plasmas'', Contrib. Plasma Phys. '''50''', 6-7 (2010) 594]]<br />
* [[doi:10.1088/0029-5515/51/9/094022|J. Sánchez et al, ''Overview of TJ-II experiments'', Nucl. Fusion '''51''' (2011) 094022]]</div>Daniellopezbruna